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Din avgränsning ger 111 träffar.

• 2017:15 Radionuclide release rates associated with bounding cases featuring relatively early canister failures in a spent fuel repository

  Background In 2011 the Swedish Nuclear Fuel and Waste Management Co (SKB) submitted a license application for construction of a geological repository for spent nuclear fuel according to the KBS-3 method, comprising of copper canisters, bentonite buffer, backfill and surrounding crystalline bedrock. The post-closure safety assessment of the repository, SR-Site, has been reviewed by the Swedish...

  Innehållstyp: Publikationer

• 2013:24 Modelling of nuclear fuel cladding under loss-of-coolant accident conditions

  We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postulated loss-of-coolant accident in light water reactors. The model treats the Zr alloy solid-to-solid phase transformation kinetics, cladding creep deformation, oxidation and rupture as a function of temperature and time in an integrated fashion during the transient. The fuel cladding material...

  Innehållstyp: Publikationer

• 2014:20 An evaluation of high-temperature creep of zirconium alloys: data versus models

  In this report Dr Massih presents correlations for creep in different phases of zirconium alloys and also presents a general solution to the difficulty of accurately describing the material properties in phase transition for several zirconium alloys. Based upon superplasticity relations, models are adapted to fit with experimental data for materials in transition regions. The creep models are...

  Innehållstyp: Publikationer

• 2011:16 Modelling of ultrasonic testing of cracks in cladding

  During the last two decades, SSM has supported research to develop a model for the non-destructive test situation based on ultrasonic technique. Such a model is important in many ways, for example to supplement and plan experimental studies and to perform parametric studies in qualification situation. Modeling can be a useful tool when the inspection system shall be technically justified.

  Innehållstyp: Publikationer

• 2011:13 Investigation of Discrete-Fracture Network Conceptual Model Uncertainty at Forsmark

  Flow modelling using alternative assumptions regarding conceptual and parametric uncertainty in the spatial and structural relationships among fractures indicates elevated flow rates and groundwater velocities to deposition holes compared to SKB’s flow modelling results. Simulated sampling of fractures in boreholes does not indicate any reason to exclude the proposed spatial and structural...

  Innehållstyp: Publikationer

• 2000:13 Utvärdering av omgivningskontrollprogrammet vid kärnkraftverken och Studsvik

  De kärntekniska anläggningarna utför årligen omgivningskontroll i närområdet enligt ett program utarbetat av SSI. En mer omfattande utvärdering av programmet har genomförts baserat på närmare 20 års erfarenheter och mätdata. Resultaten visar att i den terrestra miljön detekteras de högsta halterna och det största antalet...

  Innehållstyp: Publikationer

• 2020:01 Sulphide-induced stress corrosion cracking and hydrogen absorption incopper exposed to sulphide and chloride containing deoxygenated water at 90°C

  SSM perspektiv Bakgrund Den metod som den svenska kärnkraftsindustrin planerar att tillämpa för att slutförvara använt kärnbränsle kallas för KBS-3 och bygger på tre skyddsbarriärer: kopparkapslar, bentonitbuffert och det svenska urberget. I den aktuella KBS-3-utformningen kommer det använda kärnbränslet att placeras i en insats...

  Innehållstyp: Publikationer

• 2022:11 Kingdom of Sweden IRRS ARM Summary Report 2022

  The IAEA Integrated Regulatory Review Service Mission to Sweden in November 2022...

  Innehållstyp: Publikationer

• 2023:11 Study of degradation of spent fuel’s structural material and core components under long-term wet storage

  SSM perspective Background Sweden is managing the spent nuclear fuel and core components from its commercial nuclear reactors with a national strategic plan. The fuel and core components are initially stored at the reactor site. After an on-site storage period to comply with transportation limits on decay heat and radiation, these materials are shipped to the Clab (Central Interim Storage...

  Innehållstyp: Publikationer

• 2023:14 Effect of gamma-irradiation on the redox states of the structural iron in bentonite clay

  SSM perspective Background Bentonite clay is used as buffer and backfill material which form engineered barrier in the spent fuel repository. The buffer material surrounding the copper canister will be exposed to gamma and neutron radiations, especially during the first few hundred years after closure of the repository. The redox states of the structural iron in montmorillonite, the dominant...

  Innehållstyp: Publikationer